ML19322C289

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IE Insp Rept 50-346/78-01 on 771213-15 & 780111-13. Noncompliance Noted:Failure to Use Approved Copy of Procedure AD 1839.01 for Field Implementation & Failure to Log Transient Cycle on 770924
ML19322C289
Person / Time
Site: Crane, Davis Besse  
Issue date: 01/27/1978
From: Knap R, Tambling T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19322C284 List:
References
TASK-TF, TASK-TMR 50-346-78-01, 50-346-78-1, NUDOCS 8001160804
Download: ML19322C289 (9)


See also: IR 05000346/1978001

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NUCLEAR RECULA! CRY CCMM:55!CN

OFFICE OF INSPECTICN A.'O ENTORCE.T'T

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Repor: No. 50-346'73-01

Cocke: No. 50-346

License No. N??-3

Licensee: Toledo Edisen C:=pany

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Edison Pla:a

300 Madison Avanue

Toledo, CH a3652

Fa:il :y name: Cavis-3e sse '.'ni: 1

nape::1:n at: Cavis-Besse 51:4 Cak Harbor CH

nspec:i:n :enduc:ed:

Cece=ber 13-15, 1977 and .*anuary '.1-13,

1975

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Inspe:::r:

T. N. Tambling

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Approved by:

R. C. Knop, Chief

I/17/74

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Rea::or Projec:s See:ica i

Ins ee:i:n Summar-s

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Insce::1on on December 13-13, 1977 and Januarv !!-13, 1973 (Recor: Ne .-

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50-346/73-01)

Areas Inseected: Review of licensee even: reper:s, review of design,

design :-anges and =cdifica:icns, vi:nessing of a ::ansien:

es: of 'O'

pcwer and followup :n li:ensee's evalua:1:n en Auxiliary Feedva

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problems. The inspection involved 56.5 inspector-heurs ensi:e by one

NRC inspector.

Resui:s: Cf :he four areas inspec:ed, no 1:e=s of ncncompliance

were -found in three areas; one apparen: 1:es of noncompliance

was found in ene area (infraction - failure :o properly i=plemen:

.and ain:ain a procedure - Para. 3).

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Personnel Contac:ed

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  • T. Murray, S:stien Superintendent

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3. Seyer, Main:enance Engineer

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  • L. Scal:er, Technical Engineer

L. Crime, Reliabill:y Engineer

  • J. 3cek, Cpers:i:ns Quali:y Assurance Engineer
  • W. Green, Assistan: :o 5:a:ica Superintenden:
  • T. Hart, Quality Assurance Engineer
  • W. Schul::, ?:ver Ingineering and Cens: ue:ict

C. Oaf:, Quali:y Ocntrol Superviser

The inspe:::: alac :alked vi:h and in:erviewed ::her li:ensee

a :1:yees, in:luding nembers f :he :echni:a; ani engineerin; s:2f f,

Opera:1:ns s:sif and radia:icn pre:e::icn.

  • ene:es :hese a::ending ext: interview.

1.

Feties of ?enr:utine Even:s Re; r:ed by :he Licensee

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vere reviewed and evalua:ed by :he li:ensee as require: by Techni-

21 Specifica: ions, :ha: ::rre::ive ac:ica was :aken by :he li:ensee.

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endi:10ns f:: apera:ica were no: exceeded.

The inspec:or examined

sele::ed S:a:ica Review 3 card =inutes, the licensee investiga:1:n

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reper:3, legs, and records, and inspec:ed equip =en: and in:erviewed

selected persennel.

Inadver:an: baron dilu:ica due to i= proper ad'us:ed ::n:::1

valve (57-33-77-02)

Loss of Decay Hea: flev during surveillance :est of STAS

(57-32-77-05)

Mc=en:ary less of core flew in Mode 4 due :: valve _svi::hing

sequencing problem (N?-32-77-06)

Failure of Oe:ay !! eat check valve OH-77 Oc close when Core Fl:cd

Tank was unisola:ed (N?-32-77-08)

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So:h Auxiliary Teedva:er Sys:e=s ineperable (N?-30-77-11)

Ele::: lyte level above maximum level indi:2:1:n = ark :n 1 3 vol:

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ba::eries (NF-32-77-13)

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Loss of Makeup Pumps due :o bl:vn control cir:ui: fuse (NP-32-77-la)

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C:eling va:er :: Auxiliary Feedva:er ?u=p bearing improperly aligned

(N?-32-77-17)

Auxiliary Feedva:er ? ump turbine g:vernor valve .>ibra:ed :losed

(NP-32-77-13 and ?ar: 21 reper:, L. E.

Ree :: J. O.

k'e p pl e r , R!l!

da:ed Nove=ber 16, 1977)

Inadver:an: 5?AS ac:ua:i n in Mode 3 ::upled with 1:s3 : f .' 2 ^ '!A C 'l

b u s p. , , , . . . . .,:-;> iz~ue,

Tailure of :ve con:r:1 ::c: e:ergency da ;ers :: mee: res;:nse

time during :es:ing (.','?-33-77-09)

Loss of SFA5 channel 1 due :: .:ss :f *;"!

dis:ribu:i:n panel

(N?-33-77-14)

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0:ntain=en: in:ernal pressure n:: bein: meni:: red

';?-33-7~-16)

Energency 'lenti.a:i:n Sys:e= 1-1 in perable (N?-33-77-3 3

Ele::: lyte level in s:a:ien ba::eries high (N?-33-77-27)

Con:ain=en: personnel air lock in:erlock inoperab'e (NF-33-77-35)

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5:eas generator level indica:ica cu: side differen:ial : lerance

(NP-33-77-aa)

Decay Hea: isola:1:n valves DH-11 and CH-12 declared in perable

(N?-33-77-50)

The inspec:or no:ed tha: :he licensee had iden:ified and corre::ed

four 1:e=s related to :hese events.

No o:her 1:e:s of nonce:pliance or devia:icns were identified.

During the ext: interviev :he inspe:::: reques:ed supplemen:a1

repor:s for NP-32-77-IS, NP-33-77-06 and N?-33-77-14 :o cover :he

final corre :ive ac:icns, concurred vi:h :he licensee's interPreta:icn

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he post-LOCA flow pa:h th:: ugh OH11 and !! (NF-33-77-30), dia:ussed

interpretations regarding surveillance :es:ing and no:ed impr:vement

in :he. closing out of recen: DVR's associa:ed with non-rou:ine repor:s.

1

The following licensee event reports were reviewed and closed ou:

on the bases of an inoffice review and evalua:1:n:

3

Loss of Shield Building in:egri:y (N?-33-77-32)

Con:ainment isolation valve C'.*-3074 ineperable (5?-33-77-33)

Main Steamline hydrauli: snubber 3R17 and 5111 inoperab' e

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Makeuo Pu:p 1-2 rencved f : service :: all:w main:enan:e (N?-32-

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Oe:ay Hea: Valve Pi: opened :a perf::s wiring change (N?-33-7'-77)

I?S channe'. 1 a::iden:'y de-energi:ed (N?-33-77-73)

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Ccvernor valve closed en A?? ;-2 (N?-33-77-30)

I'.'S :: sin 1-3 delta pressure ::nt :11er malfun::1:n '57-33-77-941

Diesel genera::: : ip :n :verspeed (N?-33-77-95)

Cen:::' K:c: isolati:n ds=per would no: ::=ple:ely close (N?-3 3- 7 7-9 5 )

Failure of AF 3872, S:cp valve between ATT l-2 and 3:eam Generator

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(NF-33-77-33)

3.

Reduction of Discharge Cvele Limi:s en Pressuri:e: Relief '!alves.

LIR NP-32-77-12

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The inspec:s reviewed :he.~l.i_cen_s.ee_'s_repe.. ,r' tid

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to determine whe:her :he cc ree:ive ac:Lon Jasatid7Augsst?97_1977,$

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being ' imp 1'e=.en:ed.

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'41:hin this review on Dece=ber 14, 1977 :he inspec:or f und :ha:

a log of Opera:icnal ::ansien:s was being sain:sined in :he con::31

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room. However,

a.

An unapp cved copy of AD 1339.01, Occumenta:icn of All:Wable

Opera:ing Transien: Cycles, was being used in :he field for

i=plemen:stion,

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The ac:uation of :he pressuriser relief valve RC-2A

on September 21, 1977, had no: been 1:gged.

c.

The curren: revision (Revisien 1) of AD 1339.01 li:1:acion

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for the nu=ber of cycles and te=peratures limits on the

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pressuri:er relief valves was not in agree en: vi:h ?! $164.03,

(Revisien 0) Pressuri:er Power Relief Valve Periodi: Test.

The failure :o use an approved ::py of AD 1339.01 for field i ple-

en:stion. :s log :he ::ansian: cycle en Sep: ember

2',

1977, and to

revise A0 1339.01 to reflec: curren: 11:1:a:icns is considered :: 'e

an 1:e= of nen:: pliance wi:h :he require en:s of Se::icn 5.3.1 Of

he Technical Specif1:2:1:n.

The licensee i=nedia:ely replaced :he unappr:ved ::py of A0 1339.01

wi:h an appr:ved c:py.

n :ne exi: in:erview :he li:ensee

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s revise AD 1339.01 :: reflec: :he corree: lizi:s, reviev :he

transien: lag :: insure : hat i:ers are being recorded pr:cerly,

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record :he :e:pera:ure a: :he :ime of pressuri:er relief valves

a::ua:icns, and :o evalua:e hev they vi'1 assess pressuri:er re'ief

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  • salve ac:ua:icas a: differen: :e:pera:ures.

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Con: sin =en: Is:la:icn Valve RC 2iCA :neperable, L R N?-3 3-77-10

The inspec::: reviewed the licensee's reper: da:ed Augus: 26, 1977,

o de: ermine :he s:a:us of :he corre::ive ac:icn. A1:heugh :he

ini:ial corre::ive ac:1:n had been ::=ple:ed, DVR 74-1 had n::

been :losed ou: and the invas:igation by :he archi:e::/ engineer

was no: available for review by :he inspec:or. This 1:e re=ains

unresolved pending :he close out of :he DVR and :he inves: iga: ion.

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Circular 77-13, Reactor Safe:v Siznals Negated Durin Ves:ing

The inspec:or reviewed with :he li:ensee his ::nclusien and a::icas

on Cir:ular 77-13.

The licensee had ::ncluded :ha: : heir proce-

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dures and manage en: con:rol syste=s were adequa:e :o preven:

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similar occurrence, however, the referenced incident was being used

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as a basis of a special : raining secessi:n for opera:ing and plan:

persennel :o de: ens:ra:e :he possible ::nsequences of no: adhering :o

precedures and controls.

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Oesign, Desian Chantes and Medifica:10ns

The inspec:or revie.ed i=ple=en:ing precedures and sele::ed

Facili:y Change Reques: f r:s :o de:er=ine whe:her changes :o

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he facili:y were =ade in accordance vi:h 10 CFR 30.39, :he

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Technical Specifica:icns and es:ablished QA/QC and ad=inis::2:ive

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con::als. The review included :he f:ll:ving i=plemen:ing pr:cedures.

Quality Assurance ,rocedure

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,esign c.on::c .

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Administrative ?:ocedure '.3-3.00, Changes, Test and Experi:ents.

Rev. O.

?:ver Engineering Ins::ucti:n 031, 210, resign Changes, Tes:s, and

Experimen.s. Rev. 3.

?:ver Engineering Instru::i:n 02*.-3 2 . 5af e:y Feview/Evaluati:n/

Acciden: Analysis. Rev. 1.

?cuer En3ineering ins:: ::icn 22.'-:3., %:r'-; Fackage,

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A: the ext: interviev :he inspe:::: dis: ssed severs' areas in

A3 13a5.00 that should be clarif*ed. ~hese . era:

3e::1:n 2.3 - The p:: cessing cf n:n-nuclear safe:y rela:ed design

nanges shculd be defined.

Se::Lon 4.2 - The defini: ion of Nu: lea: Safe:y Rela:ed should be

expanded to includ: ::her chapters :f the F3AR.

10 CFR Par: 50.39

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addresses :he FSAR and no: Only Chapter 15.

Also, A3MI 1: ems are

no addressed.

Secticn 3 - See: ion 6.5.1.6 of :he e:hnical specifica:icns sta:es

cha: SR3 vill reviev tests, experimen:3, :hanges :: nodifications

ha: affec: nuclear safe:y. Nuclear saft:y as used :here has a

much b cader scope :han i= plied in section 4.2.

Section 6. 9 and 6.10 - These see:

who is responsible for prepara:ica of :es:1:ns need :o be clarified as :o

p::cedures, the

informa:1on required in :he procedures and :he for=a: :: be used.

Section 9.5 - This se : ion should be clarified that a delega:ed

represen:ative can ac: for :he ? ojec: Engineer :o insure :ha:

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es:ing and ac:ep;ance cri:eria are ne: before re:arning :he

affec:ed equi;=en: :o service.

The folleving selected Facili:7 Change Require =ents were reviewed.

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FCR 77-221

AT?T Speed Con:::1 Relay Modifica:1:n

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FCR 77-199

Modification of Wiring n AF?T Cen:r01 Relays

CW/ AUX and CCW/ACX

FCR 77-154

Pressure Cecrs 215, 601 and 602

FCR 77-417

CROC3 - Trip 3reakers

TCR ~7-C26

Pr: posed Te:hnical Specifi:2:icns change f::

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Propcsed Te:hnical Specifi:a:i:n Change :: I73

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Change 175 f eita ? Call Range f r:

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.tr: posed Tecnnica; Specift:2:i:n Change n 5:ea:

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Cenera::: Level Transmi::ers

FCR 77-120

Separa: ion of NI-

and ';;-2 Cable Runs

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Medi:.ication :o IVS 31 veu: Panel Se: points

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The inspector found these f acility change re ces:s in various s:a:es

of c =pletion vi:5 :he caster copies in circulation f::

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review and

approval.

In the ext: interviev the inspec:Or discussed :he general

s:a:us of closing out c::pleted FCR's and s:a:ed :ha: :he final review

of TCR's veuld be unresolved pending an upda:ing of the licensee's

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files. This was due in part that the licensee was engaged in an

effer: to elese cu: outstanding FCR's.

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licensee Internal Audits

'a'hile reviewing the licensee's implemen:a:icn of design changes

and =odification (?acili:y Change Requests, Paragraph 6), :he

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inspec:or noted :ha: :he li:ensee had iden:ified an 1:e

associa:ed with the implementa:1cn ' procedures QA?

2030 and AD 1845.

3.

Auxiliarv Feedvate Svstems

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As a resul: of an inoffice review of problems vi:h :he auxiliary

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feedva:e sysee=s, a :elephene ::nversa:icn :n December 12, *977,

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was held wi:h represen:stives of the licensee :o de: ermine wha:

special ac:1:n : hey were :aking :: insure :he reliabili:7 Of the

sys:e=s. Cn Dece=ber 13, 1977, :he licensee s:a:ed : hey v:uld:

Complete an engineering evaluati:n of :he auxiliary feedwa:e: pump

control syste: to deter ine if the system is ade ua:e.

Veuld in:: ease :he surveillance :es:ing fr:: =cn:hly :: week y.

Would no: p :ceec above 75P pcwer if any :::a p :b'e:s ievel: ped

un:ii both :he li:ensee and :ne ';RC ::c;d evalua:e :he pr:ble (s).

On January 12, .' 973, :he li:enses ::::' e:ed an engineering eva;ua:i:r

of :he auxiliary f eedva:er system p 05;ers including a f ailure en

ece:be: ;3, 1977.

This evalua:1:n and :he sss::12:ed sys:e: ::ci-

fi:a:icns were reviewed by :he inspec:::.

The resui:3 Of :he

evaluation and cdifica:icns were dis:ussed in :he ex::

in:erview.

9.

Unresolved ::e s

Unresolved i:e:s are za::ers abcu: vn :h scre ini:rna:1:n is

required in order :o ascer:ain whe:her : hey are ac:ep;able 1:e:s*

ita:s of senc pliance or deviations. . Unresolved i:e=s disclosed

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during inspectica is discussed in Paragraphs 4 and 6.

10.

? ver Ascensi:n Tes:ine. T? 300.1;

The inspec::: vi:nessed :he performance of I? 300.14, '

Reac:or/ Turbine Trip perfor ed December 15, 1977 f :=

40: Power.

Overall perfor:ance was evaluated, including

adherence :: :es: procedure and =ee:ing of acceptance

cri:eria.

No 1: ems of nonce:pliance or deviations were iden:ified,

11.

Ext: In t erview

The inspec:o: =e: vi:h licensee repreten:a:ives (denoted in ? ara-

graph 1) on- ece ber 13, 1977 and Janut:7 13. 1973.

The inspec:::

summari:ed the scope and findings of :ht

inspec:1:n.

The licensee

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represen:a:ive made :he following remarka in respense :o cer:ain

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of the.1: ems discussed by :he inspec:::.

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Acknowledged :he s:2:e=en: by :he inspe :or vich respect :o :he

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1: ems of non===pliance (?aragraph 3).

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Acknowledged :he inspe::s 's reques: ':: supplemen:ary closecut

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reports :o spec 1#ied 11:ensee even: repor:s (?aragraph 0).

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Acknowledged the inspec:c:'s sta:e=ent :ha: :: :1:secut o f '.EF.

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NP-33-77 'O would remain unresolved pending :he closcout o' the

inves: iga:1:n (?aragraph 4).

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